Conclusions
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1.
Domestic and foreign experience indicate that quantitative analysis of the reliability of reactor systems during their development is a rather effective means of increasing their reliability.
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2.
The introduction of quantitative reliability analysis into engineering practice is impeded because of inadequately developed engineering methods applicable, in particular, to reactors for atomic power stations.
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3.
A variant of the engineering technique for estimating the structural reliability of reactors is proposed. This method enables calculations to be made of the reliability of a broad class of installations and their subsystems during the design stage with satisfactory accuracy and generality.
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4.
A particular (simplified) case of this method, the exponential model, was considered. Based on the example of a calculation of the reliability of the reactors in the first and second units of the Beloyarsk Atomic Power Station it was shown that this model can give a good approximation to the actual situation, is simple, and is conveniently applied.
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Literature Cited
W. Vesely, Nucl. Engng. and Design,13, No. 2, 337–360 (1970).
G. Mieze, Kerntechnik,12, No. 9, 377–387 (1970).
I. A. Ryabinin, Elements of the Theory and Computation of the Reliability of Marine Electrical Power Systems [in Russian], Sudostroenie, Leningrad (1972).
E. Dressler, Kerntechnik,4, No. 12, 574–581 (1972).
A. Colombo, Survey and Critical Analysis of Programs for System Reliability Computation. Commission of the European Communities, CCR, Ispra, Italy (1971).
E. Woodcock, The Calculation of Reliability of Systems. The Program NOTED. UKAEA-AHSB(S), R117 (1968).
B. Garrik, Nucl. Engng. and Design,13, No. 2, 245–321 (1970).
J. Spanier and E. Gelbard, The Monte-Carlo Method and Neutron Transport Problems [Russian translation], Atomizdat, Moscow (1972).
P. I. Popov and V. G. Terent'ev, Reliability of Automated Systems [in Russian], Izd. MIFI, Moscow (1966).
P. I. Popov and A. P. Cherenkov, Avtmatika i Telemekhanika, No. 9, 143–151 (1968).
P. I. Popov and A. P. Cherenkov, in: Control of Nuclear Power Stations [in Russian], Vol. 4, Atomizdat, Moscow (1970), pp. 119–133.
B. P. Demidovich et al., Numerical Methods in Analysis [in Russian], Nauka, Moscow (1967).
R. Barlow and F. Proshan, Mathematical Theory of Reliability [Russian translation], Sovetskoe Radio, Moscow (1960).
Additional information
Translated from Atomnaya Énergiya, Vol. 37, No. 5, pp. 408–416, November, 1974.
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Emel'yanov, I.Y., Klemin, A.I. & Polyakov, E.F. Methods of estimating the reliability of nuclear reactor installations. At Energy 37, 1163–1172 (1974). https://doi.org/10.1007/BF01245598
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DOI: https://doi.org/10.1007/BF01245598